ML20084R618

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Safety Evaluation Supporting Amends 201 & 191 to Licenses DPR-77 & DPR-79,respectively
ML20084R618
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 06/01/1995
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20084R595 List:
References
NUDOCS 9506090351
Download: ML20084R618 (3)


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NUCLEAR REGULATORY COMMISSION i e WASHINGTON, D.C. 2055M001

%..,*!SAFETYEVALUATIONBYTHEOFFICEOFNUCLEARREACTORREGULATIO RELATED TO AMENDMENT N0. 201 TO FACILITY OPERATING LICENSE N0. DPR-77 AND AMENDMENT NO.191 TO FACILITY OPERATING LICENSE NO. DPR-79 TENNESSEE VALLEY AUTHORITY SE0V0YAH NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 1.0 INTRODVCTION By application dated April 6,1995, the Tennessee Valley Authority (the licensee) proposed an amendment to the Technical Specifications (TS) for Sequoyah Nuclear Plant (SQN) Units 1 and 2.

The requested changes would modify Definition 1.9, " Core Alteration," Definition 1.25, " Quadrant Power Tilt Ratio," and Unit 1, Table 1.1, " Operational Modes." The proposed changes are modeled after the Westinghouse Electric Corporation Standard TS (STS),

NUREG-1431.

2.0 EVALUATION 2.1 Core Alteration Definition Presently, the SQN TS define Core Alteration as " movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel." A broad interpretation of this wording could include such items as underwater lights, nylon ropes, or hand-held tools that are commonly used in the reactor vessel during refueling outages. However, a review of the use of the core alteration term in the TS and STS indicate that it is intended to address only those items that could affect core reactivity.

Therefore, the licensee has proposed changing the definition to limit its applicability to the movement of any fuel, sources, reactivity control components, or other components affecting reactivity within the reactor vessel with the head removed and fuel in the vessel. This wording also agrees with the definition used in the STS (with the exception that the licensee has added the words "other components affecting reactivity," which strengthens the definition but does not change its intent). The staff agrees that Core Alterations is intended to refer to actions that have the potential of affecting core reactivity and, therefore, finds the change acceptable.

2.2 Ouadrant Power Tilt Ratio (0PTR) Definition The proposed change to Definition 1.25, " Quadrant Power Tilt Ratio," would remove the sentence: "With one excore detector inoperable, the remaining three detectors shall be used for computing the average." This instruction is inappropriately located and conflicts with TS Surveillance Requirement (SR) 4.2.4.2, which provides instructions for obtaining the QPTR with one Power Range Channel inoperable using the movable incore detectors.

(The power Range 9506090351 950601 PDR ADOCK 05000327 P

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/ l Channels are excore detectors.) The purpose of-the proposed change, j

therefore, is to remove the conflict.between the definition and the SR. This-change also results in specifying a method of determining QPTR that is consistent with the STS when a power range channnel is inoperable.

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addition, it would remove the required actions when a channel is -inoperable i

from the definition. Therefore, the staff finds the change acceptable.

j 2.3 Operational Modes Table The proposed chang'e to Table 1.1, " Operational Modes," affects Unit 1 TS only I

and will result in consistency with Table 1.1 in the Unit 2 TS. The three l

changes are:

(1) to change percent rated power from "25%" to ">5%" for the Power Operation Mode, (2) change the average coolant temperature limit from

">350'F" to "2350*F" for the Hot Standby Mode, and (3) change the average coolant temperature limit from 140*F" to "$140*F" for the Refueling Mode. The first two changes are consistent with the STS and the last is a plant-specific j

limit. These changes are administrative in nature, do not affect operation or operational limits of the unit, and are, therefore, acceptable.

3.0 STATE CONSULTATION

In accordance with the Comission's regulations, the Tennessee State official was notified of the proposed issuance of the amendment. The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

The. amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (60 FR 20531). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

5.0 CONCLUSION

The Comission has concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Comission's regulations, and (3) the issuance of the amendment will not be inimical to the comon defense and security or to the health and safety of the public.

Principal Contributor: David E. LaBarge Dated: Jtme 1,1995 i

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Mr. Oliver D. Kingsley, Jr.

SEQUOYAH NUCLEAR PLANT o

Tennessee Valley Authority cc:

Mr. O. J. Zeringue, Sr. Vice President TVA Representative Nuclear Operations Tennessee Valley Authority Tennessee Valley Authority 11921 Rockville Pike 38 Lookout Place Suite 402 1101 Market Street Rockville, MD 20852 Chattanooga, TN 37402-2801 Regional Administrator Dr. Mark 0. Medford, Vice President U.S. Nuclear Regulatory Commission Engineering & Technical Services Region II Tennessee Valley Authority 101 Marietta Street, NW., Suite 2900 3B Lookout Place Atlanta, GA 30323 1101 Market Street Chattanooga, TN 37402-2801 Mr. William E. Holland Senior Resident Inspector Mr. D. E. Nunn, Vice President Sequoyah Nuclear Plant New Plant Completion U.S. Nuclear Regulatory Commission Tennessee Valley Authority 2600 Igou Ferry Road 3B Lookout Place Soddy Daisy, TN 37379 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael H. Mobley, Director Division of Radiological Health Site Vice President 3rd Floor, L and C Annex Sequoyah Nuclear Plant 401 Church Street lennessee Valley Authority Nashville, TN 37243-1532 P.O. Box 2000 Soddy Daisy, TN 37379 County Judge Hamilton County Courthouse General Counsel Chattanooga, TN 37402-2801 Tennessee Valley Authority ET 11H 400 West Summit Hill Drive Knoxville, TN 37902 Mr. P. P. Carier, Manager Corporate Licensing Tennessee Valley Authority 4G Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Ralph H. Shell Site Licensing Manager Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37379